Thesis topics in EEME

Application deadline: 11th June 2025

Modeling of Safety and Environmental Consequences of Accidents in SMR/HTGR Reactors for Industrial Applications: Assessment of Radioactive Release and Transport in Urban and Industrial Environments
- Supervisor: prof dr hab. Mariusz Dąbrowski
- Auxiliary Supervisor: dr Piotr Kopka
- Description: The development and deployment of Small Modular Reactors (SMR) and/or High-Temperature Gas-Cooled Reactors (HTGR) are gaining attention due to their potential applications in industrial sectors, such as providing process heat for chemical industries or other commercial uses. This research focuses on the integration of such reactors within industrial or nearby environments. Given the potential risks associated with these reactors, particularly the possible release of radioactive materials in the event of an accident, a key aspect of the research is the analysis of the consequences of failures leading to the release of radioactive substances into the atmosphere.
  This work will focus on modeling the transport of radionuclides in the environment and considering specific characteristics of urbanized or industrial spaces, such as airflow patterns, wind tunnels, and local environmental factors. These considerations are essential to evaluate the emergency preparedness and response plans, particularly regarding the behavior of radionuclides and their potential impact on human health and the environment.
  The aim of this doctoral research is to model a hypothetical domain for HTGR reactors, conduct a series of accident simulations, and analyze their consequences. The research will contribute to the development of new procedures and recommendations for risk management. Existing transport models will be adapted to reflect the specific conditions of urban and industrial environments, allowing for accurate assessment of potential radiation doses.
  The project will also involve the validation of the models and a deeper analysis of the need for specialized modeling techniques in this area of research, particularly in relation to emergency preparedness, response strategies, and the impact of reactor accidents in populated areas. The outcomes will inform safety protocols and the integration of these reactors in industrial settings while ensuring public health and safety.
- Funding: NCBJ
Universal Cask for Storage, Transportation, and Disposal of HTGR Spent Nuclear Fuel
- Supervisor: prof. dr hab. Tomasz Kozlowski
- Auxiliary Supervisor: dr Agnieszka Boettcher
- Description: High-Temperature Gas-Cooled Reactors (HTGRs) utilizing TRISO fuel present new challenges for the backend nuclear fuel cycle. These reactor systems generate spent nuclear fuel (SNF) with unique characteristics—high burnup, high temperature, and graphite-based matrices—that differ significantly from traditional light-water reactor (LWR) SNF. A critical gap in current SNF management is the lack of universal storage, transportation, and disposal canister optimized for TRISO-based SNF. This project proposes the development of a universal cask system suitable for TRISO SNF that integrates storage, transportation, and direct disposal functionality without requiring repackaging, therefore enhancing safety, efficiency, and cost-effectiveness. The project objectives are to design or modify a dual-purpose canister (DPC) that meets the mechanical, thermal, criticality, and radiological requirements of TRISO SNF for storage, transportation, and the final permanent disposal.
- Funding: NCBJ
Nuclear production of emission free hydrogen
- Supervisor: prof. dr hab. Wacław Gudowski
- Auxiliary Supervisor: dr eng. Mateusz Nowak
- Description: Hydrogen is increasingly seen as a key component of future energy systems if it can be made without carbon dioxide emissions. It is starting to be used as a transport fuel, despite the need for high-pressure containment.
  Hydrogen can be combined with carbon dioxide to make methanol or dimethyl ether (DME) which are important transport fuels. Hydrogen also has future application as industrial-scale replacement for coke in steelmaking and other metallurgical processes.
  Nuclear energy can be used to make hydrogen either electrolytically or with high-temperature reactors thermochemically.
  The objective of the PhD is to assess all options for nuclear production of hydrogen, select the system which is optimal for the polish conditions and make economical assessment of future hydrogen systems together with a preconceptual design of modular hydrogen production unit.
- Funding: NCBJ
Modelling a zero power Dual Fluid Reactor
- Supervisor: prof. dr hab. Konrad Czerski
- Auxiliary Supervisor: dr eng. Hisham Elgendy
- Description: Dual Fluid Reactor (DFR) is one of the most advanced reactor concepts combining a high operating temperature of about 1000°C with fast neutron spectrum, which would lead to very effective production of electricity, industrial heat, and hydrogen. Its unique features have been already studied in many modelling works involving the neutron production and thermal hydraulics. However, before the new technology can be implemented, a long development process is necessary. The best method to demonstrate the technology is to use small facilities that are able test all important physical and chemical processes.
  In the next future, a zero power DFR demonstrator is planned to be constructed. It will be strongly simplified compared to the final construction, but its main features as neutron energy spectrum, self-regulation of the reactor, heat exchange between fuel and coolant can be fully tested. The aim of the doctoral thesis will be to propose the most effective tests of the DFR demonstrator and model its response in dependence of the proposed parameters. The simulations performed will create the basis for future experiments.
- Funding: NCBJ
Designing Experimental Thermal Molten Salt Loops Dedicated for HTR Application as a Technological Heat Source
- Supervisor: prof. dr hab. Jerzy Cetnar
- Auxilliary Supervisor: dr eng. Tomasz Kwiatkowski
- Description: This research aims to design and develop experimental thermal molten salt loops that can be integrated into experimental nuclear reactors to serve as technological heat sources for high-temperature reactor (HTR) applications. The project will focus on the thermal and hydraulic design of the molten salt loop, considering factors such as heat transfer efficiency, material compatibility, and the integration of the loop into the reactor environment. The molten salt loop will be tested under various operational conditions, including steady-state and transient scenarios, to evaluate its performance in transferring heat from the reactor core to external systems. The study will also address the challenges of high-temperature operation, corrosion resistance, and the impact of radiation on molten salt properties. By embedding the test loop within an experimental nuclear reactor, the research will provide valuable data on the feasibility and effectiveness of molten salt as a heat transfer fluid in HTR systems.
  Objectives of the PhD project:
  • Design and optimization of molten salt loops for high-temperature heat transfer in HTRs, including material selection and flow design.
  • Investigation of thermal-hydraulic behavior and heat transfer efficiency of molten salt loops under different operating conditions.
  • Study of the compatibility of molten salts with structural materials in the reactor environment, especially in terms of corrosion resistance and long-term stability.
  • Development of experimental setups for integrating molten salt loops into experimental nuclear reactors for real-world testing of heat transport systems.
  • Evaluation of the impact of radiation on the properties and performance of molten salt as a heat transfer fluid.
- Funding: NCBJ